| Packages with Keyword: COMPLEX GEOMETRY |
| Package Name | Abstract | RSICC Tapelist | Title |
| 3DDT | Abstract | C00605 C6600 00 | Multigroup Diffusion Code System for Use in Fast Reactor Analysis. |
| ACOH | Abstract | C00191 I3675 00 | Aerojet COHORT Monte Carlo Code System. |
| AIRTRANS | Abstract | C00110 I3675 00 | Monte Carlo Time and Energy-Dependent Three-Dimensional Radiation Transport Code. |
| AKERN | Abstract | C00190 C0000 00 | Aerojet Point Kernel Integration Calculational System. |
| AKERN | Abstract | C00190 U1108 00 | Aerojet Point Kernel Integration Calculational System. |
| ALBEMO | Abstract | C00268 C6600 00 | Albedo Monte Carlo Code System. |
| ARC | Abstract | C00224 C6600 00 | Aircraft Radiation Transport Code System, Crew Dose Calculation. |
| AT123D | Abstract | C00417 I0360 00 | Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in an Aquifer System. |
| BERMUDA | Abstract | C00616 FV260 03 | Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors. |
| BETA II | Abstract | C00117 C6600 00 | Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
| BETA II | Abstract | C00117 I0360 00 | Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry. |
| BMC-MG | Abstract | C00291 C6600 00 | Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium. |
| BOLD VENTURE IV | Abstract | C00459 I3033 00 | A Reactor Analysis Code System. |
| BOT3P-5.3 | Abstract | P00530 MNYCP 02 | Code System for 2D and 3D Mesh Generation and Graphical Display of Geometry and Results for Radiation Transport Codes. |
| CAFDATS | Abstract | P00549 MNYCP 00 | Converter of Angular Fluxes of DORT, ANISN and TORT Systems. |
| CALOR95 | Abstract | C00610 MNYWS 00 | Monte Carlo Code System for Design and Analysis of Calorimeter Systems, Spallation Neutron Source (SNS) Target Systems, etc. |
| CAVEAT | Abstract | C00169 I3675 00 | General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry. |
| CGS 11.4 | Abstract | P00243 MFMWS 03 | Common Graphics System. |
| CITATION-LDI 2 | Abstract | C00643 PC386 02 | Nuclear Reactor Core Analysis Code System. |
| CNCSN 2009 | Abstract | C00726 PCX86 01 | One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Parallel Multi-Threaded Code System. |
| COG11.1 | Abstract | C00829 MNYCP 00 | Multiparticle Monte Carlo Code System for Shielding and Criticality Use. |
| COHORT-II | Abstract | C00198 I7094 00 | General Purpose Monte Carlo Radiation Transport Code System. |
| CONDOS-II | Abstract | C00416 I0360 00 | Code for Estimating Radiation Doses from Radionuclide-Containing Consumer Products. |
| DANTSYS 3.0 | Abstract | C00547 MFMWS 01 | One-, Two-, and Three-Dimensional, Multigroup, Discrete-Ordinates Transport Code System. |
| DDXCODES | Abstract | C00583 FM380 00 | One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections. |
DIF3D 11.2892
FEDC | Abstract | C00784 MNYCP 02 | Code System Using Variational Nodal Methods and Finite Difference Methods to Solve Neutron Diffusion and Transport Theory Problems. |
| DOORS 3.2A | Abstract | C00650 MFMWS 04 | One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System. |
| DOSE 1 | Abstract | C00165 I3675 00 | Gamma-Radiation Dosimetry for Arbitrary Source and Target Geometry. |
| DRAGON3.05D | Abstract | C00647 MNYWS 03 | Lattice Cell Code System. |
| EASY-QAD 2.0.1 | Abstract | C00744 PC586 02 | A Visualization Code System for Gamma and Neutron Shielding Calculations. |
| EGS4 | Abstract | C00331 MNYCP 00 | Monte Carlo Simulation of the Coupled Transport of Electrons and Photons. |
| ELPHO | Abstract | C00301 I0360 00 | Three-Dimensional Monte Carlo Electromagnetic Transport Code System. |
| ESP | Abstract | C00193 I0360 00 | General Purpose Monte Carlo Neutron Transport Code System. |
| FASTER III | Abstract | C00168 U1108 00 | Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
| FASTER-III | Abstract | C00168 I3675 00 | Monte Carlo Neutron and Photon Transport Code System in Complex Geometries. |
| FE3DGW | Abstract | C00531 D0780 00 | Code System for Finite-Element, Three-Dimensional Ground-Water Flow Analysis. |
| FINELM | Abstract | C00483 MFMWS 00 | Multigroup Finite Element Diffusion Code System. |
| FOCUS | Abstract | C00390 I3033 00 | Adjoint Monte Carlo Neutron Transport Code System. |
| FOTELP-2014 | Abstract | C00581 MNYCP 04 | Monte Carlo Simulation of Photons, Electrons and Positrons Transport. |
| G3-6ED | Abstract | C00075 C6600 00 | Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
| G3-6ED | Abstract | C00075 I3033 00 | Kernel Integration Code System - Multigroup Gamma Ray Scattering. |
| GADJET | Abstract | C00115 C6600 00 | Monte Carlo Gamma-Ray Adjoint Energy Transport Code in Complex Three-Dimensional Geometry. |
| GGG-GP | Abstract | C00564 IBMPC 00 | Kernel Integration Code System - Multigroup Gamma-Ray Scattering Using the GP Buildup Factor. |
| GNOMER | Abstract | C00625 MNYCP 01 | Multigroup 3-Dimensional Neutron Diffusion Nodal Code System with Thermohydraulic Feedbacks. |
| GREAT-GRASS | Abstract | C00143 I3675 00 | Monte Carlo Radiation Transport Code Systems for Fallout Shielding. |
| GRENADE | Abstract | C00516 C1787 00 | Green's Function Nodal Algorithm for the Diffusion Equation. |
| GRENADE | Abstract | C00516 D0780 00 | Green's Function Nodal Algorithm for the Diffusion Equation. |
| GUI2QAD-3D | Abstract | C00697 PC586 01 | A Graphical User Interface for QAD-CGPIC, a Point Kernal Code for Neutron and Gamma-Ray Shielding Calculations in Complex Geometry. |
| HAM | Abstract | C00267 U1108 00 | Monte Carlo Multigroup Neutron and Photon High Altitude Transport Code System. |
| HEATING 7.3 | Abstract | P00199 MNYCP 06 | Multidimensional, Finite-Difference Heat Conduction Analysis Code System. |
| HERAD | Abstract | C00444 CY00I 00 | Three-Dimensional Monte Carlo Computer Code System for Calculating Radiation Damage from Ion Beams. |
| HERMES-KFA | Abstract | C00687 MNYWS 00 | Monte Carlo Code System for High-Energy Radiation Transport Calculations. |
| HEXAB-3D | Abstract | C00593 I0370 00 | Three-Dimensional Few-Group Coarse Mesh Diffusion Code for Neutron Physics Calculation of Reactor Core in Hexagonal Geometry. |
| INAP | Abstract | C00235 U1108 00 | Improved Neutron Activation Prediction Code Systems. |
| ISO-PC 2.1 | Abstract | C00636 IBMPC 01 | Kernel Integration Code System for General Purpose Isotope Shielding Analyses. |
ITS6
FEDC | Abstract | C00792 PCX86 00 | Integrated TIGER Series of Coupled Electron/Photon Monte Carlo Transport Codes System. |
| KAMCCO | Abstract | C00325 I0370 00 | Three-Dimensional Time Dependent Monte Carlo Code System for Fast Neutron Physics Problems. |
| KAP-VI | Abstract | C00094 U1108 00 | Kernel Integration Code System in Complex Geometry. |
| KERNEL | Abstract | C00672 IBMPC 00 | Monte Carlo Code System for Electron (Positron) Dose Kernel Calculations. |
| LAHET 2.8 | Abstract | C00696 MFMWS 00 | Code System for High Energy Particle Transport Calculations. |
| MAP | Abstract | C00150 I3675 00 | Kernel Integration Code System in Complex Geometry with Special Application to Surface Sources Determined by Discrete Ordinates Calculations. |
| MARC-PN | Abstract | C00311 D8810 00 | A Neutron Diffusion Code System with Spherical Harmonics Option. |
| MARMER | Abstract | C00579 D8350 00 | A Flexible Point-Kernel Shielding Code System. |
| MARMER | Abstract | C00579 PC486 00 | A Flexible Point-Kernel Shielding Code System. |
MCNP6.3.1-EXE
810 | Abstract | C00870 MNYCP 03 | Monte Carlo N-Particle Transport Code System. |
MCNP-DSP-EXE
810 | Abstract | C00699 MNYCP 01 | Monte Carlo N-Particle Transport Code System with Digital Signal Processing based on MCNP4A. |
MCNPX-POLIMI-EXE
810 | Abstract | C00791 MNYCP 01 | Monte Carlo N-Particle Transport Code System To Simulate Time-Analysis Quantities. |
| MERCURE 4-82 | Abstract | C00142 I3033 00 | Three-Dimensional Code System for Integrating Multigroup Line-of-Sight Attenuation Kernels by Monte Carlo Techniques. |
| MEVDP | Abstract | C00157 C6600 00 | Primary Radiation Transport Code System - Complex Geometry - Computerized Anatomical Model Man. |
| MKENO-DAR | Abstract | C00513 FM380 00 | Direct Angular Representation Monte Carlo Code for Criticality Safety Analysis |
| MOCA | Abstract | C00590 IPCAT 00 | Monte Carlo Criticality Code System for Hexagonal Geometries. |
MONK 6.3
FEDC | Abstract | C00393 I3033 00 | A General Purpose Monte Carlo Neutronics Code System. |
| MORSE-ANSI STD. | Abstract | C00127 I3675 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-B | Abstract | C00368 I0370 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-C | Abstract | C00431 C7600 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 C0000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 CY000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 D0VAX 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 I0360 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CG | Abstract | C00203 U0000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-CGA | Abstract | C00474 ALLCP 03 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSEC-SP2 | Abstract | P00142 H6000 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-E | Abstract | C00258 I0360 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-EMP | Abstract | C00588 IBMPC 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-H | Abstract | C00471 I3081 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-L | Abstract | C00261 C6600 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MORSE-SGC | Abstract | C00277 C7600 00 | Monte Carlo Multigroup Neutron and Gamma-Ray Transport Code System. |
| MOSRA-LIGHT | Abstract | P00505 MNYWS 00 | High-Speed Three-Dimensional Nodal Diffusion Code System. |
| MULTI-KENO2 | Abstract | C00492 FM380 00 | A Monte Carlo Code System for Criticality Safety Analysis. |
| NESTLE 5.2.1 | Abstract | C00641 MNYCP 04 | Code System to Solve the Few-Group Neutron Diffusion Equation Utilizing the Nodal Expansion Method (NEM) for Eigenvalue, Adjoint, and Fixed-Source |
| NMTC/JAM | Abstract | C00717 PC586 00 | High Energy Particle Transport Code System. |
| O6R | Abstract | C00128 I3675 00 | A General-Purpose Monte Carlo Transport Code System. |
| OGRE | Abstract | C00046 I3675 00 | A General-Purpose Monte Carlo Gamma-Ray Transport Code System. |
| OMEGA | Abstract | C00433 BESM6 00 | Monte Carlo Criticality Code System. |
| PATCH-7 | Abstract | C00243 C0074 00 | Three-Dimensional Kernel Integration Code-Explicit Single Scattering Option. |
| PF-COMP | Abstract | C00106 C3600 00 | Building Fallout Radiation Protection Factor Analysis. |
| PKI | Abstract | C00573 C0830 00 | A Point Kernel Integration Code For Radiation Shielding of Loop System. |
| POLYRES | Abstract | P00438 MNYCP 00 | Richards Equation Solver; Rectangular Finite Volume Flux Updating Solution. |
| PROCIV | Abstract | C00488 U1110 00 | A Code System for Calculating the Protection Factors Against Radioactive Fallout for Apartment Buildings. |
| PTRAN | Abstract | C00618 PC386 00 | Proton Monte Carlo Transport Program for the PC. |
| PUSHLD | Abstract | C00271 C0074 00 | Gamma-Ray Three-Dimensional Calculation of Dose Rates from Plutonium in Various Geometries. |
| PUTZ 2.1 | Abstract | C00595 IBMPC 00 | A Point-Kernel Photon Shielding Code. |
| QAD | Abstract | C00048 I0360 00 | Kernel Integration Code System. |
| QAD-BSA | Abstract | C00346 C0000 00 | Kernel Integration Code System. |
| QAD-CGGP-A | Abstract | C00645 MNYCP 00 | Kernel Integration Code System. |
| QADMOD-G | Abstract | C00396 I3033 00 | Point Kernel Gamma-Ray Shielding Code With Geometric Progression Buildup Factors. |
| QADMOD-GP | Abstract | C00565 IBMPC 00 | Point Kernel Gamma-Ray Shielding Code With Geometric Progression Buildup Factors. |
| QAD-P5 | Abstract | C00048 C6400 00 | Kernel Integration Code System. |
| QAD-QC | Abstract | C00401 C0000 00 | Kernel Integration Code System. |
| QAD-QC | Abstract | C00401 I0360 00 | Kernel Integration Code System. |
| QAD-UE | Abstract | C00448 H6000 00 | Kernel Integration Code System. |
| RAFFLE/2 | Abstract | C00279 C0176 00 | A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option. |
| RAFFLE/2 MOD 2 | Abstract | C00279 I0360 00 | A General Purpose Monte Carlo Code System for Neutron Transport with Mixed Zone Geometry Option. |
| REBEL 3 | Abstract | C00299 I0360 00 | Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
| REBEL-2 | Abstract | C00299 C6600 00 | Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
| REBEL-2 | Abstract | C00299 ICL00 00 | Adjoint Monte Carlo Calculation of Radiation Doses to Human Organs in Dwelling Rooms. |
| REBUS3/VARIANT8 | Abstract | C00653 MNYWS 01 | Code System for Analysis of Fast Reactor Fuel Cycles. |
| REBUS-PC 1.4 | Abstract | C00708 PC586 00 | Code System for Analysis of Research Reactor Fuel Cycles. |
| S3 | Abstract | C00322 C6600 00 | Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
| S3 | Abstract | C00322 DVX11 00 | Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
| S3 | Abstract | C00322 IBMPC 00 | Kernel Integration Code System--Multigroup Gamma-Ray Scattering. |
| SALE3D | Abstract | P00443 CY000 00 | ICEd-ALE Treatment of 3-D Fluid Flow. |
| SAM-CE | Abstract | C00187 C6600 00 | Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations. |
| SAM-CE | Abstract | C00187 I0360 00 | Monte Carlo Time-Dependent Complex Geometry (Combinatorial) Code System for the Solution of the Forward Neutron and Forward and Adjoint Gamma-Ray Transport Equations. |
| SAM-CEP | Abstract | C00192 C6600 00 | Monte Carlo Code System Correlated to the Simultaneous Solution of Multiple, Perturbed, Time-Dependent Neutron Transport Problems in Complex Three-Dimensional Geometry. |
| SANDYL | Abstract | C00361 C0000 00 | A Monte Carlo Three-Dimensional Code System for Calculating Combined Photon-Electron Transport in Complex Systems. |
| SCAP-82 | Abstract | C00418 C7600 00 | Single Scatter, Albedo Scatter, or Point Kernel Analysis Code System in Complex Geometry. |
| SCORE-EVET | Abstract | P00442 C7600 00 | Code System for Three-Dimensional Hydraulic Reactor Core Analysis. |
| SERA-1C1 | Abstract | C00729 MNYCP 01 | Simulation Environment for Radiotherapy Applications. |
| SHADRAC(G-30) | Abstract | C00084 I7090 00 | Kernel Integration Code - Shield Heating and Dose Rate Calculation in Complex Geometry. |
| SIGMA II | Abstract | C00118 C6000 00 | Space Radiation Dose Analysis Within Complex Configurations. |
| SIGMA II | Abstract | C00118 PC486 00 | Space Radiation Dose Analysis Within Complex Configurations. |
| SIXTUS-3 | Abstract | C00609 MFMWS 00 | Three-Dimensional, Nodal, Neutron Diffusion Criticality Code System in Hex-Z Geometry. |
| SKYIII-PC | Abstract | C00289 IBMPC 01 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SKYSHINE-III | Abstract | C00289 D0VAX 00 | Calculation of the Effects of Structure Design on Neutron, Primary Gamma-Ray and Secondary Gamma-Ray Dose Rates in Air. |
| SNAP-3D | Abstract | C00434 MNYCP 01 | Multigroup Complex Geometry Neutron Diffusion Code System. |
| STREAM | Abstract | C00321 C7600 00 | A Three-Dimensional Cylindrical-Geometry Monte Carlo Ray Tracing Code for Computing Light Transmission. |
| TART2022 | Abstract | C00638 MNYCP 09 | Coupled Neutron-Photon, 3-D, Combinatorial Geometry, Time Dependent, Monte Carlo Transport Code System. |
| THIDA-2 | Abstract | C00410 FM380 00 | Code System for the Calculation of Transmutation, Activation, Decay Heat and Dose Rate in Fusion Reactors. |
| THT | Abstract | C00480 I0360 00 | Three-Dimensional Neutron Coarse Mesh Code System to Evaluate Average Bundle Fluxes and Power in Light Water Reactors. |
| TIMOC-72 | Abstract | C00144 I0370 00 | Monte Carlo Three-Dimensional Neutron Transport Code System. |
| TITAN 1.29 | Abstract | C00759 PCX86 04 | A Three-Dimensional Deterministic Radiation Transport Code System. |
TRIPOLI-4 8.1
OECD | Abstract | C00806 MNYCP 00 | Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport Calculations. |
| TRISTAN | Abstract | C00511 HM280 00 | Multigroup Three-Dimensional Direct Integration Method Radiation Transport Analysis Code System. |
| TRITAC | Abstract | C00560 D8810 00 | A Three-Dimensional Transport Code For Eigenvalue Problems Using The Diffusion Synthetic Acceleration Method. |
| TRUMP | Abstract | P00522 MNYCP 01 | Code System for Transient and Steady-State Temperature Distribution in Multidimensional Systems. |
| VCS | Abstract | C00262 I0360 00 | Coupled Discrete Ordinates-Adjoint Monte Carlo Calculation of Radiation Protection Factors in Vehicles. |
| VENTURE-PC | Abstract | C00654 PC586 02 | A Reactor Analysis Code System. |